用氢氧化镁包埋氧化镁废弃物的水合硅酸镁砂浆的研制

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
M. Baxter Chinery , H.S. Wong , M.R. Wenman , C.R. Cheeseman , L.J. Vandeperre
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引用次数: 0

摘要

一种减少英国遗留镁诺克斯废物体积的新方法是将富含Mg(OH)2的污泥作为镁硅酸盐水合物(M-S-H)砂浆的组成部分。本研究着眼于将模拟腐蚀镁污泥(CMgS)纳入达到封装标准的砂浆中的潜力。最佳的M-S-H砂浆粘结剂摩尔比为0.5,砂浆中有46.6%是CMgS污泥。该砂浆60天抗压强度为25 MPa, 6个月连接孔隙率为6.5%,满足废包封砂浆的要求。这项工作证明了将从Magnox Swarf Storage Silos获得的富Mg(OH)2污泥作为M-S-H砂浆的原材料用于废物封装的潜力,同时节省了相关的成本和空间。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Development of magnesium-silicate-hydrate mortars using magnesium hydroxide for Magnox waste encapsulation
A novel approach to reduce the volume of the UK legacy Magnox waste is to use the Mg(OH)2-rich sludge as a component in a magnesium-silicate-hydrate (M-S-H) mortar. This study looks at the potential to incorporate a simulant corroded magnesium sludge (CMgS) into a mortar that achieves the encapsulation criterion. The optimum M-S-H mortar has a binder molar ratio of 0.5, resulting in 46.6 wt% of the mortar being CMgS sludge. This mortar had compressive strengths of 25 MPa at 60 days with a connected porosity of 6.5 % at 6 months, and this meets the requirements for a waste encapsulated grout. The work demonstrates the potential to use a Mg(OH)2-rich sludge, obtained from Magnox Swarf Storage Silos as a raw material in M-S-H mortars in waste encapsulation, with associated cost and space savings.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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